High-fidelity MCNP modeling of a D-T neutron generator for active interrogation of special nuclear material
- 1. University of Michigan, Ann Arbor, MI 48109 (United States)
Description
Fast and robust methods for interrogation of special nuclear material (SNM) are of interest to many agencies and institutions in the United States. It is well known that passive interrogation methods are typically sufficient for plutonium identification because of a relatively high neutron production rate from 240Pu . On the other hand, identification of shielded uranium requires active methods using neutron or photon sources . Deuterium-deuterium (2.45 MeV) and deuterium-tritium (14.1 MeV) neutron-generator sources have been previously tested and proven to be relatively reliable instruments for active interrogation of nuclear materials . In addition, the newest generators of this type are small enough for applications requiring portable interrogation systems. Active interrogation techniques using high-energy neutrons are being investigated as a method to detect hidden SNM in shielded containers . Due to the thickness of some containers, penetrating radiation such as high-energy neutrons can provide a potential means of probing shielded SNM. In an effort to develop the capability to assess the signal seen from various forms of shielded nuclear materials, University of Michigan Neutron Science Laboratory's D-T neutron generator and its shielding were accurately modeled in MCNP. The generator, while operating at nominal power, produces approximately 1x1010 neutrons/s, a source intensity which requires a large amount of shielding to minimize the dose rates around the generator. For this reason, the existing shielding completely encompasses the generator and does not include beam ports. Therefore, several MCNP simulations were performed to estimate the yield of uncollided 14.1-MeV neutrons from the generator for active interrogation experiments. Beam port diameters of 5, 10, 15, 20, and 25 cm were modeled to assess the resulting neutron fluxes. The neutron flux outside the beam ports was estimated to be approximately 2x104 n/cm2 s.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nima.2010.08.053Additional details
Identifiers
- DOI
- 10.1016/j.nima.2010.08.053;
- PII
- S0168-9002(10)01827-9;
Publishing Information
- Journal Title
- Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment
- Journal Volume
- 652
- Journal Issue
- 1
- Journal Page Range
- p. 120-123
- ISSN
- 0168-9002
- CODEN
- NIMAER
Conference
- Title
- 12. Symposium on radiation measurements and applications (SORMA)
- Dates
- 24-28 May 2010
- Place
- Ann Arbor, MI (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44001785
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BEAMS; DEUTERIUM; DOSE RATES; MEV RANGE; NEUTRON FLUX; NEUTRON GENERATORS; PHOTONS; PLUTONIUM; PLUTONIUM 240; RADIATION DETECTION; RADIOACTIVE MATERIALS; THICKNESS; TRITIUM; URANIUM
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BOSONS; DETECTION; DIMENSIONS; ELEMENTARY PARTICLES; ELEMENTS; ENERGY RANGE; EVEN-EVEN NUCLEI; HEAVY NUCLEI; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MASSLESS PARTICLES; MATERIALS; METALS; NEUTRON SOURCES; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; PARTICLE SOURCES; PLUTONIUM ISOTOPES; RADIATION FLUX; RADIATION SOURCES; RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; STABLE ISOTOPES; TRANSURANIUM ELEMENTS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.